ML17252B481

LER 76-061-00 for Dresden, Units 2 and 3 Re During Testing of HPCI Test Return Line, Which Was Suspected to Be Leaking, Was Found That Contamination Demineralized Water Was in Fact Leaking from the Underground Pipe Into the Storm Sewer

ML17252B481
Person / Time
Site:	Dresden
Issue date:	10/14/1976
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS LTR 76-732 LER 76-061-00
Download: ML17252B481 (3)

Text

• Commom9th Edison*.-:

Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. //76-732 October 14, 1976 Mr._James G. Keppler, Regional Dire Directorate of Regulatory Operati .

U. S. Nuclear Regulatory Commiss ~

• 799 Rodsevelt Road ~

Glen. Ellyn, Illinois 60137

REFERENCES:

Docket No. 50-237 Docket No. 50-249 En~losed please find Reportable report ntimber 50-237/1976-61. This report is be~ng to yotir office in accordance with the Dresden Nuclear Power Station Technical.

1 Specifications, Section 6.6.B.

~ln.{4,Lc,

~~. B. Stephe_n,E!on... .

r":- ***~t'a ti 0°Il . s t'l p' ~"f'i'n t e'n*d en t Dresden Nuclear Power Station BBS:jo Enclosure cc: .. Director of Inspection & Enforce~ent

• Director of Mariagement tnformation & Program Control file./NRC

LICENSEE EVENT *REPORT .. * .

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LICENSEE LICENSE EVENT

• ** NAME LICENSE NUMBER TYPE . TYPE

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REPORT REPORT CATEGORY TYPE. SOURCE OOCKl;:T NUMBER EVENT DATE REPORT DATE

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' 7 8 57 58 59 60 69' 74 75 EVENJ ..DESCRIPTION .

[fil?]** !:DURING- TESTING- OF TH£ HPC I' T£sT EETVRN LINE;> WHICH WAS SUSPEC..IED' I,.

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'7 8 9 11 12 80 OFFSITE CONSEQUENCES .

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• NA 7 8 9, 80 LOSS OR DAMAGE TO FACILITY TYPE ' DESCRIPTION

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EVENT DESCRIPTION (Continued) had no effect on HPCI system operability, There have be.en pre.v:lously reported leaks in HPCI system piping at. Dresden, (50-237 /1976-61)

CAUSE DESCRIPTION (Continued) believed that the leak had slowly developed since June, 1971 when the line was hydrostatically.tested following a repair, Based on a conservative estimate of 5.o*x 104 µµ Ci/! in the condensate storage tanks, a leakage ra:te of 5 gpm, and a. dilution flow rate of 5.0 X 104 gpm, the maximum discharge canal activity attributable to the two-hour HPCI test each month was 5.0 X io-9 µ Ci/ml, or 5%

of the Tech Spec limit. Since canal discharges are normally limited to a maximum of 50% of the Tech Spec limit, a scheduled release occurring concurrently with HPCI testing would not have resulted in excessive discharge .canal activity. The estimated total activity released over the five-year period was 7,15 X 10"""3 Ci.

Health and safety implications. of this event, therefore*,' were minimal.

Because the leak is located directly below the nitrogen storage facility, the HPCI testc-return 1:ine. w.ill be rerouted: to facilitate -repairs. Completion of this repair.will satisfactorily eliminate the leakage problem.